ML041730201

Final Section C Operating for Salem, Units 1 and 2

ML041730201
Person / Time
Site:	Salem
Issue date:	06/02/2004
From:	Conicella N Public Service Enterprise Group
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-272/04-301, 50-311/04-301
Download: ML041730201 (35)

Text

Appendix D Form ES-D-1 Malf. No.

Event Type*

---

I-------- N CRSlPO R

RO Facility:

SALEM 1 & 2 Scenario No.:

NRC #I Op-Test No.: HOTEL Examiners:

Operators:

Initial Conditions:

Turnover:

Unit 2 is at 90% power with the following equipment is out of service: SA EDG taken 00s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for injector maintenance, 21 RHR Pump taken 00s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for coupling alignment. Maintenance on both components expected to be completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now. All required surveillances are complete. Weather conditions are normal. Unit 1 is at 100% power. Hope Creek is in a refueling outage. Shift orders are to raise power to 100% at 10% per hour.

90% Rated Thermal Power, MOL, Equilibrium Conditions Event Description Raise Reactor Power Event F

~~

11 4 I VCOl73A I -------------

21 Cntmt Fan Coil Unit Trip (TS CRS) 2 BFOlO5A&B RP0059A&B RP0058 PR0020A RP318G5 3

M ALL Mn Feed Pumps Trip on High Exh Hood Pressure, A M, Pzr Safety 2PR3 Fails Open C

CRSlPO 23 Aux Building Exhaust Fan Fails to Start on SEC

~

~~~

SW0215A SW0339E PRO01 6A

~

C CRSlPO I

CRSlRO

~

~

21 SW Pump Trip With Failure of 25 Service Water Pump to Auto Start Pressurizer Pressure Channel I Fails Low (TS CRS)

Decreasing Condenser Vacuum I LL I

5 I CN0086 6

7 Terminate after SI flow reduction evaluation in LOCA-1

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page I of 12 NUREG-I 021, Draft Revision 9

SIMULATOR SETUP

1.

2.

INITIAL CONDITIONS I

Initialize simulator to IC-I 91, 90% power, MOL, CB 869 ppm Clearance tag 2A EDG

4.

5.

I 3.

I Clearance tag 21 RHR Pump Pzr Press and Level Ch I selected for control and recorder 21 Cntmt Fan Coil Unit running in high speed 1

No -

1.

2.

3.

4.

5.

6.

7.

8.

9.

IO.

11.

12.

13.

Description AN0253, SER 253 Fails: G29 Priming Tank

6.

I PZR Safety Valve 2PR3 fails open when turbine governor valve 22MS29 is 4 5 % open (MONP100~0.15)

Delay Ramp Remotel Initial Final Event Value Value No No NolNo 0

1 RP0059A, Failure of Man Rx Trip RP0059B, Failure of Man S i l k Trip RP0058, Failure of Auto Rx Trip' No No NolNo NA True No No NolNo NA True No No NolNo NA True RP318G5,23 AB Exh Fn Fails to Start on SEC SW0339E, 23 SW Pump Press SW Fails Hi No No NolNo NA True No No NoINo NA True SWO215A, 21 SW Pump Trip PRO01 6A, Pzr Press Ch I (PT455) Fails Low VCOl73A, 21 Cntmt Fan Coil Unit Trip I

No I

No I

3lNo I True I True I No No 1lNo NA True No No 2/No NA 1700 CN0086, Loss of Main Condenser Vacuum2 BF0105A, 21 Stm Gen Feed Pump Trip BFOI 05B, 22 Stm Gen Feed Pump Trip PR0020A, Pzr Safety Valve 2PR3 Fails Open Page 2 of 12 No 00:03:00 4lNo 0

50 No No 5lNo 0

3 00:00:07 No 5lNo 0

3 No No No16 NA True NUREG-1021, Draft Revision 9

REMOTE FUNCTION

SUMMARY

RH26D, 21 RHR Pump Bkr Control Pwr RH27D, 21 RHR Pump Rack Out DGIOA, 2A Diesel Gen Locked Out I No No No NoINo Off off No No NoINo Tagged Tagged No No NolNo Yes Yes Description No 00:00:10 No No Delay Ramp Remote Initial I

1 I /Event I Value I :::L I

~

No 7/NO Start stop No TINO Start stop No 8lNo Untagged Tagged No 9INo On off

1.

2.

3.

No

1.

2.

3.

4.

Description Delay Ramp Remote I

Event 8440, OVDl RTB A Trip Switch No No NoINo 8441, OVDI RTB B Trip Switch No No NoINo C310,2E6D Pressure Heater Bus 480V Open No No NolNo Switch C510,2G6D Pressure Heater Bus 480V Open No No NoINo Switch

4. I DG11 D, 2A DG Bkr Control Power I

No I

No I NolNo I off I off I Initial Value off off Off off I 5. I DG12D,2ADGBkrRackOut I

No I

No I NoINo I Tagged I Tagged I Final Value off off off Off

9.

RP07D, 21 MG Set Motor Bkr RP08D, 22 MG Set Motor Bkr PR34D, PORV Stop Valve 2PR6 Tagged CT191 D, 21 CFCU 125 VDC Breaker UO OVERRIDE

SUMMARY

I I

I I

I I

1.

2.

3.

Open Reactor Trip Breakers 3 minutes after directed by crew. Delete overrides on RBs, then B440, 8441, RTB "A" and "B" open switch to ON. Also, open following breakers:

RT-7, RP07D 21 Rod Drive MG Set Motor Breaker RT-7, RP08D 22 Rod Drive MG Set Motor Breaker Once the crew has reduced reactor power by approximately 10% on decreasing vacuum, change RT-4 Final Value = 100, Ramp = 0O:OO:OO If requested, turn power off to 2PR6 using Remote Function PR34D, PORV Stop Valve toggled to Tagged on RT-8 Page 3 of 12 NUREG-1021, Draft Revision 9

' 4.

Page 4 of 12 Collect trend data on the following for evaluators:

Reactor Power Turbine Generator Load (MW)

Condenser Vacuum Pressurizer pressure (not Ch I / PT455)

SG NR level (all SGs)

SG WR level (all SGs)

NUREG-1021, Draft Revision 9

Op-Test No.:

1 Scenario No.:

1 Event No.:

1 II Time II Position Applicant's Actions or Behavior CRS Directs activities associated with power increase

- rod motion

- dilution

-turbine loading

- rod motion

- dilution (Procedure S2.OP-SO.CVC-O0OS(Q))

Coordinates with RO to initiate power increase

- operate turbine controls to establish loading rate (Procedure S2.OP-SO.TRB-0001 (Q)

- load dispatcher

- operations management RO Adds positive reactivity PO CRS Makes necessary notifications II 11 Event

Description:

Unit is at 90% power. Shift orders are to raise power to 100% at 10% per hour.

SIMULATOR OPERATOR:

1.

Use RT-1 to trigger next event (21 SW Pump Trip) on cue from lead examiner.

Page 5 of 12 NUREG-1021, Draft Revision 9

Op-Test No.: I Scenario No.:

1 Event No.:

2 Event

Description:

21 SW Pump Trip With Failure of 25 SW Pump to Auto Start PO 11 Time I Position I

ADDlicant's Actions or Behavior Observes alarms associated with 21 SW Pump trip (OHA B-13,8-14).

PO CRS PO CRS L

Determines that 25 SW Pump has failed to auto start. Recommends manually starting an idle pump.

Directs manual start of 25 SW Pump. May enter AB.SW-0001. May order the start of another idle pump.

Manually starts 25 SW Pump or other idle pump as directed by CRS.

Initiates maintenance / troubleshooting activities PO CRS PO CRS Determines that 25 SW Pump has failed to auto start. Recommends manually starting an idle pump.

Directs manual start of 25 SW Pump. May enter AB.SW-0001. May order the start of another idle pump.

Manually starts 25 SW Pump or other idle pump as directed by CRS.

Initiates maintenance / troubleshooting activities SIMULATOR OPERATOR:

1.

Use RT-2 to trigger next event (Pzr Press Channel Failure) on cue from lead examiner.

Page 6 of 12 NUREG-I 021, Draft Revision 9

Time Position Applicant's Actions or Behavior ResDonds to alarms (D-16. E-12. E-281.

RO RO RO CRS RO RO CRS CRS CRS/RO SIMULATOR OPERATOR:

1.

2.

Use RT-8 to open power breaker for 2PR6 PORV Stop Valve when requested by crew.

Use RT-3 to trigger next event (21 Containment Fan Coil Unit Trip) on cue from lead examiner.

~~

Identifies failure of Pzr Press Ch I Places Pzr Press Master Controller in MANUAL, adjusts demand to current pressure.

Implements AB.PZR-0001. Directs RO to

- adjust Master Controller output to value obtained from Attachment 1

- select alternate pressure control channel

- return Master Controller to AUTO Selects alternate pressure channel for pressure control Places Master Controller in AUTO Directs removal of the failed Pressurizer Pressure Channel from service IAW S2.0P-SO.RPS-O003(Q), Placing Pressurizer Channel In Tripped Condition Refers to TS. Enters TSAS 3.3.1.I.

Action 6 and 3.3.2.1 b. Action19 for failed channel. Enters TSAS 3.4.5b for PORV 2PR1 not operable in AUTO.

Close 2PR6 PORV Stop Valve Page 7 of 12 CRSlRO NUREG-1021, Draft Revision 9 Direct NE0 to open breaker for power to 2PR6 PORV Stop Valve

Op-Test No.:

I Scenario No.: 1 Event No.:

4 Event

Description:

21 Containment Fan Coil Unit Trip Time Position Applicant's Actions or Behavior CRS/RO/PO Recognize indications of problem PO PO PO CRS Refers to S2.OP-AR.ZZ-0011 (a), for Low Air Flow console alarm NOTIFY the SMlCRS to refer to Technical Specifications Refers to S2.OP-SO.CBV(Q), to start the standby CFCU (#25)

Enters TS 3.6.2.3 Action a I7 dav LCO)

SIMULATOR OPERATOR:

1.

2.

3.

4.

When dispatched as NEO, report back odor of burnt insulation. Appears all 21 CFCU breakers affected.

If directed to rack out breakers, request assistance from maintenance electricians because of apparent damage to breaker cubicles.

Use RT-9 to open 21 CFCU 125 VDC breaker.

Use RT-4 to trigger next event (decreasing vacuum) on cue from lead examiner.

Page 8 of 12 NUREG-I 021, Draft Revision 9

Position CRS/RO/PO CRS PO RO Op-Test No.:

1 Scenario No.:

1 Event Event

Description:

Decreasing Condenser Vacuum L

No.:

5 Amlicant's Actions or Behavior Recognize indications of decreasing vacuum:

- loss of generator megawatts

- high dissolved oxygen alarm

- rise in condenser backpressure

-Alarm OHA G-5, CNDSR VAC LO

- Alarm OHA G-13, CNDSR VAC LO-LO Implements S2.OP-AB.COND-0001 (a), Loss of Condenser Vacuum. Directs actions IAW procedure

- initiates Attachment 1, Continuous Action Summary

- dispatches operators to look for source of problem per Attachment 2

- directs start of all available condenser vacuum pumps

- directs load reduction at 5 5% per min to attempt to stabilize condenser press

- when required (backpressure > limit in Att 4), initiate rapid load reduction

- implement S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction

-when necessary, orders manual reactor and turbine trips Performs actions as directed to address decreasing vacuum:

- dispatches operators to look for source of problem per Attachment 2

- starts all available condenser vacuum pumps

- performs turbine load reduction Performs actions as directed to address decreasing vacuum:

- dispatches operators to look for source of problem per Attachment 2

- coordinates with PO to reduce turbine and reactor power

- maintains Tavg on program

- energizes pressurizer heaters

- initiates boration SIMULATOR OPERATOR:

1.

2.

Increase severity of vacuum leak to 100% with no ramp after crew has reduced reactor power 21 0% or at discretion of lead examiner.

Use RT-5 to trigger next event (trip of main feed pumps) after increasing size of vacuum leak.

Page 9 of 12 NUREG-1021, Draft Revision 9

Op-Test No.: I Scenario No.: I Event No.:

6 Event

Description:

Both Main Feed Pumps Trip, A M, Pzr Safety 2PR3 Fails Open Time Position II I Ro II I CRS RO CRS CRS CRS/RO/PO II I CRS 11 1 CRS/RO/PO Amlicant's Actions or Behavior Recoanizes both main feed wmDs triDDed. Orders manual reactor trim Performs initial actions of EOP-TRIP-I

1. MANUAL Reactor Trip:

First Handle to Trip.

Second Handle to Trip.

RTBs to open.

E6D and G6D to open.

2. Trip not confirmed.

3. MANUAL Turbine Trip.

4. Initiate Control Rod Insertion.

Transitions to EOP-FRSM-1 CRITICAL TASK #I Manually trip the main turbine within 30 seconds of diagnosis of ATWT conditions.

Verifies AFW flow >44E4 Ibm/hr Starts 21 and 22 Charging Pumps Verifies BITflow and SJI, 2,4,5,12, 13 open Verifies CV40.41.68 &69 closed Verifies >I 00 charging flow Dispatches NE0 to open RTBs and Rod Drive MG Set Breakers Dispatches NE0 to close WR70 andl5ls Verifies SI component actuation IAW APPX-3.

Verifies all PRNls 5%

Verifies IR startup rate negative Directs chemistry to sample RCS Directs STA/Rx Eng to perform SDM calculation Returns to EOP-TRIP-1 Verify immediate actions of EOP-TRIP-1 Stops all RCPs with RCS pressure < I 350 psig Verifies equipment alignment per EOP-TRIP-I Page I O of 12 NUREG-1021, Draft Revision 9

Op-Test No.:

1 Scenario No.:

1 Event No.:

6 Event

Description:

Both Main Feed Pumps Trip, A M, Pzr Safety 2PR3 Fails Open CRS/RO/PO CRS RO/PO PO CRS/RO/PO Performs diagnostic activities including:

LOSC SGTR LOCA Determines 2PR3 is stuck open Transitions to EOP-LOCA-1 (based on containment sump level 146 or elevated/increasing containment radiation levels)

Performs faulted SG evaluation Performs ruptured SG evaluation Resets SI, Phase A, Phase B, opens 21 and 22 CA330, and resets each SEC and resets 230V Control Centers Stops RHR Pumps Performs SI flow reduction evaluation CRS SIMULATOR OPERATOR:

1.

Open Reactor Trip Breakers 3 minutes after directed by crew. Delete overrides on RBs, then B440, 8441, RTB A and B open switch to ON. Also, open following breakers:

RT-7, RP07D 21 Rod Drive MG Set Motor Breaker RT-7, RP08D 22 Rod Drive MG Set Motor Breaker Transitions to EOP-LOCA-2 NOTE: Terminate scenario on lead examiners direction after crew has determined that SI flow cannot be reduced.

Page 11 of 12 NUREG-1021, Draft Revision 9

Time Position CRS PO RO PO II Applicants Actions or Behavior Directs PO to perform EOP-APPX-3 Determines 23 AB Exh Fan did not start Blocks SI to SEC using CMC switches on rear panel Resets C SEC I PO I Starts 23 AB Exhaust Fan NOTE: Terminate scenario on lead examiners direction after crew has determined that SI flow cannot be reduced.

ANTICIPATED EMERGENCY CLASSIFICATION FOR THIS SEQUENCE OF EVENTS:

Site Area Emergency (5.1.3)

Page 12 of 12 NUREG-I 021, Draft Revision 9

NRC #1 MODE:

1 POWER:

90%

RCS 869 BORON:

Mwe:

1070 SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS 4000 MWD/MTU, Zenon burning out slowly at 8 pcm/hr MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

2A Diesel Generator was C/T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for injector maintenance. 3.8.1.1 b action b is in effect, the next Line surveillance is due in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

21 RHR Pump was C/T 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for a coupling alignment. 3.5.2 c, action a. Maintenance on both components expected to be completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS :

Raise Power to 100% at lO%/hr. Reactivity Plan recommends 2500 gal of primary water for 10%

power increase, rods to be withdrawn as required for temperature control to All Rods Out position.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

PRIMARY:

SECONDARY:

RADWASTE:

Heating steam is aligned to unit 1.

No discharges in progress CIRCULATING WATEFUSERVICE WATER:

Appendix D Form ES-D-1 Facility:

SALEM 1 & 2 Scenario No.:

NRC #2 Op-Test No.: HOTEL II Examiners:

Operators:

Initial Conditions:

Turnover:

magnetic disturbances have been occurring. Current SMD K3. 22 AFW Pump was taken 00s 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for motor bearing replacement. AFW pump maintenance is expected to be complete 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from now. All required surveillances are complete. The crew is directed to maintain 100% Rated Thermal Power, BOL, Equilibrium Conditions Unit 2 is at 100% power. Unit 1 and Hope Creek are also at 100% power. Solar Event 1 No.

4 5

6

• (N)orr

,wer.

Malf. No.

Event N10193A CRSlRO CF81 (OVDI)

CRSlPO

~~

DA033D (RF) I ------------

TU0081 G VL0447 RP0058 RP0069 RP0073 RP0279AtkB N

CRSlPO R

RO C

ALL EL01 44 AF0183 M

ALL Event DescriDtion PRNIS Channel N41 Fails High (TS CRS) 24MSlO Relief Fails Open (Pressure Setpoint Decrease)

Failure of RTB Shunt Trip Capability (TS CRS)

Main Turbine Governor Valve 23MS29 Fails Closed SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To Trip, Auto MSLIS Fails to Actuate Loss of 2A 4KV Vital Bus and 23 AFW Pump Trip Terminate when feed flow re-established to a SG LC (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 10 NUREG-1021, Draft Revision 9

SIMULATOR SETUP I.

2.

INITIAL CONDITIONS I

Initialize simulator to IC-I 92, 100% power, BOL, C, 1145 ppm Clearance tag 22 AFW Pump No

1.

EVENT TRIGGERS I

Description Delay Ramp Remote Initial Final I Event Value Value AN0253, SER 253 Fails: G29 Priming Tank No No NolNo 0

1 I 6.

I 2A 4KV Bus Deenergizes on Reactor Trip (Control Bank C < 5 steps)

I

3.

4.

5.

MALFUNCTION

SUMMARY

I

~

RP0069, Main Turbine Interface Valve Failure No No NolNo NA True RP0073, Mn Turbine Trip Failures (Various)

No No NolNo 0

4 RP0279A, Auto MSLIS Fails to Actuate - Tm A No No NolNo NA True

~

7.

N10193A, PR Ch N41 Fails High No No 11No 0

200

8.

TU0081G, 23MS29 Turb Cntrl Vlv Fails CIS No No 41No NA True

9.

VL0447,22BF19 Fails Closed3 No 00:02:00 51No NA 0

I 2. I RP0058, Failure of Auto Rx Trip 1 1.

I No I

No I NolNo I NA I True I AFOI 83,23 Aux FW Pmp Overspeed Trip' No No 7lNo NA True

-~

1.

2.

3.

I 6.

I RP0279B,AutoMSLlSFailstoActuate-Tm B I No I

No I NolNo I NA I True I

~~

~

~

AF25D, 22 AFW Pump Bkr Control Power No No NolNo off Off AF26D, 22 AFW Pump Rack Out No No NolNo Tagged Tagged DA033D, 2AADC Bkr #I4 Rx Trip Bkr No No 31No Closed Open I IO. I EL0144, Lossof 2A4160VVital Bus I

No I

No I

No16 I NA I True I REMOTE FUNCTION

SUMMARY

I I

I I

I I

No I Description Delay Ramp Remote Initial Final I

I I /Event I Value I Value UO OVERRIDE

SUMMARY

1 Page 2 of 10 NUREG-1021, Draft Revision 9

No

2.

ATOR OPERATOR NOTES I

Description Delay Ramp Remote Initial Final

/Event Value Value CF18 OVDI, 24MS10 Press Setpt Decrease No No 2/No off On I

Trip 23 AFW Pump after PO throttles AFW (after immediate actions of EOP-TRIP-1).

After being dispatched to investigate closure of Main Turbine Governor Valve, NE0 reports EHC fluid leak on 23MS29 valve actuator.

Insert Malf VL0447,22BF19 Fails Closed (RT-5), after condensate pump stopped during rapid power reduction or at lead examiner's discretion.

Collect trend data on the following for evaluators:

Reactor power Turbine Generator load (MW) 21,22,23,24 SG NR level 21,22,23,24 SG WR level Page 3 of 10 NUREG-1021, Draft Revision 9

Op-Test No.: 1 Scenario No.:

2 Event No.:

1 Event

Description:

PR NIS Channel N41 Fails High Applicant's Actions or Behavior Observe indications of channel failure

- numerous alarms on OHA-E

- control rods stepping in

- PR NIS N41 indicating full scale high

- PCS AFD alarms Determines PR NIS Channel has failed high. Places ROD BANK SELECTOR SWITCH in MANUAL after obtaining CRS concurrence.

Identifies failed channel. Informs CRS.

Refers to S2.OP-SO.RPS-0001 (a), Nuclear Instrumentation Channel TriplRestoration to review actions for removing failed channel from service.

May also enter AB.NIS or AB.ROD-0003.

Notifies IlC Maintenance Reviews TS. Enters LCO 3.3.1.1 Actions 2 and 6 Coordinate to remove channel from service

1. DETECTOR CURRENT COMPARATOR, UPPER SECTION to PRN41

2. Verify CHANNEL DEFEAT lamp lit and OHA E-38 clears (alarm already cleared - specific NIS failure used does not cause this alarm)

3. DETECTOR CURRENT COMPARATOR, LOWER SECTION to PRN41

4. Veri@ CHANNEL DEFEAT lamp lit and OHA E46 cleared (alarm already cleared - specific NIS failure used does not cause this alarm)

5. POWER MISMATCH BYPASS to BYPASS PR N41

6. ROD STOP BYPASS to BYPASS PR N41

7. Verify 2RP4-OVERPOWER ROD STOP MANUAL BYPASS, CH 1 lit

8. Verify OHA E-31 clear

9. COMPARATOR CHANNEL DEFEAT to N41 IO. Verify COMPARATOR DEFEAT lit and OHA E-39 clear

11. At Control Rack No. 26, AXIAL FLUX DIFF MONITOR INPUT TEST SWITCH 1 to TEST

12. Contact IlC to position bistable test switches

13. Remove both AC control power fuses from N41 drawer front Reduce turbine load, if needed to restore Tavg to program If desired. return ROD BANK SELECTOR SWITCH to AUTO SIMULATOR OPERATOR:

1.

2.

If I/C directed to position bistable test switches, report that technician will be available to assist in approximately I hour.

Use RT-2 to trigger next event (MS10 fails open) after rods are returned to AUTO.

Page 4 of 10 NUREG-1021, Draft Revision 9

Op-Test No.: I Scenario No.:

2 Event No.:

2 Event

Description:

24MS10 Relief Fails Open (Pressure Setpoint Decrease)

E SIMULATOR Position CRS/RO/PO RO PO CRS PO CRS PO

~

CRS OPERATOR ADDliCanrS Actions or Behavior Observe changing plant parameters (temperature, power, steam pressure) and identify 24MS10 is open.

Reports Tavg lowering, Pzr Press Lo E-28 alarm, B/U Htrs energize in Auto alarm Attempts to determine reason for excess steam flow Enters AB.STM-0001 (Q), Excessive Steam Flow. Initiates Attachment 1 CAS.

Reports turbine electro-hydraulic control working correctly Directs RO and PO to prepare for load reduction NOTE: 24MS10 failure may be diagnose and valve closed prior to any load reduction.

Takes manual control, closes 24MS10.

Initiates action to reDair controller.

3.

Use RT-3 to trigger next event (Loss of Shunt Trip Capability) at discretion of lead examiner.

Page 5 of 10 NUREG-I 021, Draft Revision 9

Op-Test No.:

1 Scenario No.:

2 Event No.:

3 Event

Description:

Failure of RTB Shunt Trip Capability (TS CRS)

Time I

I Position Applicant's Actions or Behavior RO CRS Observes console alarm. Refers to S2.SO-AR.ZZ-O012(Q), 2CC2 Console Alarm Procedure.

Determines that shunt trip capability (not UV trip capability) is affected.

Refers to TS. Enters TS LCO 3.3.1.I Action 14 (not Action 1).

Initiates actions to reDair RTB.

CRS SIMULATOR OPERATOR:

4.

Use RT-4 to trigger next event (23MS29 fails closed) at discretion of lead examiner.

Page 6 of 10 NUREG-1021, Draft Revision 9

Op-Test No.:

1 Scenario No.:

2 Event No.:

4 Event

Description:

Main Turbine Governor Valve 23MS29 Fails Closed Position CRS/RO/PO Applicant's Actions or Behavior Observe indications of valve closure:

Megawatt load will drop rapidly as remaining governor valves open until limited by valve position limiter (VPL)

Console Alarm TavglTref dev as Tavg rises.

Steam Dumps will open to attempt to control Tavg Pressurizer pressure and level will rise due to change in Tavg, sprays open to control Dressure PO CRS RO Determines that 23MS29 has closed. Informs CRS. Dispatches NE0 to investigate.

Refers to Precautions and Limitations of S2.OP-SO.TRB-0001 (a), Turbine Generator Startup Operations. Determines need to reduce power to 5 30% at 5%

per minute. Implements S2.OP-AB.LOAD-0001 (Q), Rapid Load Reduction NOTE: CRS may direct >5% per min load reduction until functioning governor valves are off of open limit.

Initiates power reduction using rods and boration. Energizes pressurizer heaters.

Maintains rods above Rod Insertion Limit.

I PO Stops one condensate pump at -75% power.

PO Initiates turbine load reduction.

I SIMULATOR OPERATOR:

5.

6.

After being dispatched to investigate closure of Main Turbine Governor Valve, NE0 reports EHC fluid leak on 23MS29 valve actuator.

Use RT-5 to trigger next event (22BF19 closes) after condensate pump is stopped or at discretion of lead examiner.

CRS CRS Page 7 of 10 Dispatches maintenance to investigate problem with governor valve.

Notifies electric system operator and operations management.

NUREG-1021, Draft Revision 9

Op-Test No.:

1 Scenario No.: 2 Event No.:

5 Time Event

Description:

SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To Trip Position Applicant's Actions or Behavior PO PO Responds to feedwater alarms and/or notes changes in BFI 9 position.

Determines 22BF19 is closed, attempts to open in MANUAL, reports that it will not oDen.

CRS RO Orders a manual reactor trip.

Manually trips reactor RO Attempts to trip turbine. Determines turbine trip not functioning.

CRITICAL TASK #I lnltlates MSLl before completion of reading of first 4 steps of EOP-TRIP-I.

I CRS I Implements EOP-TRIP-I RO SIMULATOR OPERATOR:

7.

2A 4KV Bus will automatically de-energize on event trigger when Control Bank C < 5 steps.

Determines MSLl required. Manually initiates MSLIS Page 8 of I O NUREG-1021, Draft Revision 9

Op-Test No.:

1 Scenario No.:

2 Event No.:

6 Event

Description:

Loss of 2A 4 W Vital Bus and 23 AFW Pump Trip Position CRS RO RO PO Time Applicants Actions or Behavior Performs initial actions of EOP-TRIP-1

- Trip Reactor (had to manually trip)

- Is Reactor Trip Confirmed

- Trip Turbine (turbine would not trip, MSlVs closed)

- Is ANY 4 KV Vital Bus energized (2A de-energized)

- Is SI Actuated (SI will actuate because of failure of turbine trip)

Reports reactor tripped manually, 2 rods not fully inserted Reports turbine not tripped, MSlVs closed ReDorts 2A 4KV Bus de-eneraized. 21 EDG runnina unloaded CRS CRS CRS NOTE: Mn generator output bkrs do not auto open because turbine fails to trip. CRS may order opening of mn gen output bkrs 1-9 and 9-10 Makes page announcement - reactor trip Notifies SM of need to implement Emergency Classification Guide II RO PO CRS CRS CRS RO CRS CRS PO Verifies RCPs running, Tavg trending to 547F, trip breakers open PO reports loss of flow on 23 AFW Pump.

Dispatches NE0 to close 21SW20 (2A bus component)

Requests assistance from WCC to perform AB.4KV-0001 and investigate loss of 2A 4KV Bus Directs RO to start 22 SWGR Exh Fan NOTE: Fan appears to be running - bkr is closed but bus is de-energized Reports only 1 CCW pump running.

Dispatches NE0 to close CC37 and CC38 Directs transition to FRHS-1 when SG level ~ 9 %

with AFW flow <22E04 Ib/hr Controls AFW flow to maintain >22E04 lblhr NOTE: Use RT-7 to trigger trip of 23 AFW pump after PO throttles AFW (after immediate actions of EOP-TRIP-1).

CRSIROIPO CRS RO PO PO RO Verify RCS pressure > intact SG pressure Reviews Bleed and Feed initiation criteria with crew Stops all reactor coolant pumps Verifies condensate system in operation Reports SGFP not available due to MSLl Initiates SI Page 9 of I O NUREG-I 021, Draft Revision 9

Position CRS RO Op-Test No.:

1 Scenario No.:

2 Event No.:

6 Event

Description:

Loss of 2A 4KV Vital Bus and 23 AFW Pump Trip

~

Applicant's Actions or Behavior Directs SI Verification per EOP-APPX-3 Resets SI Resets Phase A Isolation Resets Phase B Isolation Opens 21 CA330 and 22CA330 Resets each SEC Resets 230V Control Centers SIMULATOR OPERATOR:

1.

2.

ANTICIPATED EMERGENCY CLASSIFICATION FOR THIS SEQUENCE OF EVENTS:

2A 4 W Bus will automatically de-energize on event trigger when Control Bank C.c 5 steps.

Use RT-7 to trigger trip of 23 AFW pump after PO throttles AFW (after immediate actions of EOP-TRIP-1).

Site Area Emergency (3.1.1.b AND 3.2.1.b)

OR Site Area Emergency (8.1.3.c)

PO Page 10 of 10 Closes 21 CN32 and 22CN32 NUREG-1021, Draft Revision 9 RO Stops running RHR and SI pumps. Stops either 21 or 22 Charging Pump I

CRS I Determines SG to be depressurized.

I PO I Fully opens selected MSIO I

CRS I Directs NE0 to open selected BF40 or BF19 I

PO I Opens selected BF13 I

PO I Opens 21 CN48 and 22CN48 Reports observed level increase in selected SG and/or CET temperatures I lowerina PO u

CRITICAL TASK #2 Establish condensate flow into at least one SG.

NOTE: Terminate scenario on lead examiner's direction after condensate flow has been established.

NRC #2 MODE:

1 POWER:

100%

RCS 1145ppm Mwe:

1190 BORON:

SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS 4000 MWDMTU MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

22 AFW Pump was C/T 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for motor bearing replacement, 3.7.1.2 a, action a.

Maintenance is expected to complete 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> fiom now.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS :

Orders to shift to maintain 100% power.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Solar Magnetic Disturbances have been occurring, currently there is an SMD K-3 in effect until 2300 tonight.

PRIMARY:

SECONDARY:

Heating steam is alignec, to mlr RADWASTE:

No discharges in progress CIRCULATING WATEWSERVICE WATER:

Form ES-D-1 Appendix D Event TY Pe*

N CRSlPO R

RO I

CRSlRO C

ALL C

CRSlPO C

CRSlRO M

ALL Facility:

SALEM 1 & 2 Scenario No.:

NRC #3 Op-Test No.: HOTEL Event Description Raise Reactor Power Pressurizer Level Channel I (LT459) Fails Low (TS CRS) 21 SG Tube Leak (5 gpm) (TS CRS) 21 Main Feed Pump Trip 23 RCP High Vibration SGTR with Loss of Offsite Power Examiners:

Operators:

C CRSlPO 11 Initial Conditions:

3% Rated Thermal Power, MOL 21 SI Pump Fails to Auto Start Terminate scenario when depressurization criteria met (SGTR-1 Table F)

Turnover:

bonnet leak on Pzr Spray Bypass Valve 2PS4. Mode change is approved. Weather conditions are normal. Unit 1 and Hope Creek are at 100% power. Shift orders are to raise power in preparation for placing the main turbine in service. Procedure in use: IOP-3 at Step 5.4.14.

Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to Malf. No.

PROOI7A Event 1

2 3

4 5

6 7

• (N)ormal, SG0078A BFOI 05A RCOOIPC SG0078A EL01 34 SJOI 84A (R)eactivity, Page 1 of I O NUREG-I 021, Draft Revision 9

SIMULATOR SETUP AN0253, SER 253 Fails: G29 Priming Tank PRO01 7A, Pzr Lvl Ch I (LT459) Failure INITIAL CONDITIONS No No

1.

Initialize simulator to 3% power IC-I 93

~~

5.

6.

EVENT TRIGGERS I

RC0012C, 23 RCP High Vibration EL0134, Loss of Offsite Power' No No I.

None No

1.

MALFUNCTION

SUMMARY

Description Delay Ramp Remote Initial Final

/Event Value Value None Description No

1.

Delay I

Description Delay Ramp Remote Initial Final

/Event Value Value None SG0078A, 21 SG Tube Leak I

No R i p 1 Re;;;f I l n i l I Fiial I Event Value Value NoINo I 4. I BF0105A, 21 Main Feed Pump Trip I

No I

I NA True

7.

SJ0184A, 21 SI Pp Fails to Start on SEC No No NoINo REMOTE FUNCTION

SUMMARY

I I

I I

I I

110 OVERRIDE

SUMMARY

I I

I I

I I

Page 2 of 10 NUREG-1021, Draft Revision 9

SIMULATOR OPERATOR NOTES I

1 1.

2.

3.

After 23 RCP High Vibration, ramp the severity of the SG tube leak from 5 gpm to 650 gpm over 3 minutes, then initiate the loss of offsite power.

Collect trend data on the following for evaluators:

21 and 22 SG pressure Pzr pressure 21 and 22 SG NR level Highest CET temperature NI power If contacted on SG tube leak, SM informs CRS that extra NCO will perform rad monitor plotting IAW Continuous Action Summary Steps 3 and 4 of S2.SO-AB.SG-0001 (Q).

Page 3 of 10 NUREG-I 021, Draft Revision 9

Op-Test No.: 1 Scenario No.:

3 Event No.:

1 Event

Description:

Raise Reactor Power Time Position Applicant's Actions or Behavior CRS CRS RO Directs activities associated with power increase IAW S2.OP-IO.ZZ-O003(Q), Hot Standby to Minimum Load:

- rod motion

- dilution Initiates Turbine Generator Startup Operations Adds positive reactivity

- rod motion I

I -dilution II I

I1 I PO I Places MSlOs in AUTO with setpoint I010 to 1020 psig I

SIMULATOR OPERATOR:

1.

Use RT-1 to trigger next event (Pzr Level Channel Fails Low) on cue from lead examiner.

Page 4 of 10 NUREG-I 021, Draft Revision 9

Op-Test No.:

I Scenario No.:

3 Event No.:

2 Event

Description:

Pressurizer Level Channel I (LT459) Fails Low Time Position RO CRS/RO RO RO CRS RO RO CRS CRS Andicant's Actions or Behavior Observes OHA. Identifies that Pzr Lvl Ch I has failed low.

Refers to Alarm ResDonse Procedure for OHA E-36.

Takes manual control of charging, minimizes charging flow (maintains pzr level on pgrm IA W AB.CVC Attachment 1).

NOTE: From Attachment 1. Taraet Pzr Level = 1.1875 * (Tava - 547) + 22 Selects an oaerable channel for control. alarm. and recorder.

Restores pressurizer heaters, as desired.

Directs restoration ofletdown IAW S2.OP-S0.CVC-0001 (Q), Charging, Letdown and Seal Injection NOTE: CRS may go directly to AB.CVC-0001 (a), Loss of Charging. Steps that are duplicated in AB are shown here in bold italics.

Prepares for letdown restoration:

2.

Ensures letdown orifice isolations closed (2CV3,4, 5)

3.

Ensures 2CC71 in AUTO

4.

Opens 2CV7, Ltdn Hx Inlet Vlv

5.

Places 2CV18 in MANUAL CLOSE

6.

Opens 2C18 until CLOSE (INC PRESS) p/b extinguishes

7.

Opens 2CV2 (and 2CV277), Ltdn Line lsol Vlv(s)

8.

Places 2CV2 and 2CV277 (Ltdn Line /sol Vlvs) in AUTO

9.

Places 23 Charging Pump in MANUAL andADJUSTS chg flow 85-90 gPm IO. Adjusts 2CV71, as necessary, to maintain 6-12 gpm per pump, not to exceed 40 gpm total RCP seal injection flow Restore letdown:

1.

Simultaneously

- Opens 75 gpm letdown orifice isolation (2CV4 or 2CV5)

- Adjusts 2CV71 for 6 to 12 gpm per pump

- Adjusts 2CV18 to maintain letdown pressure at 300 psig Ensures Master Lvl Controller in AUTO Ensures pzr level within normal band, places 23 Chg pump in AUTO Adjusts 2CV18 as necessary and places in AUTO

2.

3.

4.

Contacts I&C to place pressurizer channel in tripped condition (/A W S2. OP-SO. RPS-O003(Q), Placing Pressurizer Channel in Tripped Condition.)

Enters TS LCO 3.3.1.I Action 6. May review post accident monitoring TS (only 2 channels required).

SIMULATOR OPERATOR:

1.

Use RT-2 to trigger next event (SG Tube Leak) after normal letdown has been restored on cue from lead examiner.

Page 5 of 10 NUREG-I 021, Draft Revision 9

~~

Op-Test No.:

I Scenario No.:

3 Event No.:

3 Event

Description:

21 SG Tube Leak (5 gpm) r Time Position PO CRS CRS CRS CRS CRS RO RO/PO Applicant's Actions or Behavior Reports increasing activity in cond offgas (R15) and 21 SG BID Sample (R19A)

Refers to AB.RAD-0001 (Q), Abnormal Radiation NOTE May go directly to AB.SG-0001 (Q), Steam Generator Tube Leak Announces increasina activitv on 21 SG

~

PO CRS Notifies SM to refer to Emergency Classification Guide

~~

~

~

~

~

Closes 21GB4,21 MSI 8,21 MS7 Dispatches NE0 to close 21 MS45,23 AFW Pump Turbine Steam Supply Refers to AB.SG-0001 (Q), Steam Generator Tube Leak CRS CRS RO Reviews Attachment 1, CAS.

Verifies pressurizer level stable Dispatches operators to align SGBD and sampling Directs chemistry to sample and determine leak rate Calculates RCS leak rate Identifies 21 SG as affected SG CRS CRS II I PO I Sets 21 MSI 0 to 1045 psig Makes notifications Enters TS LCO 3.4.7.2.c. Action b. for greater than 1 gpm total SG tube leakage and greater than 500 gpd tube leakage in single SG (4 hrs to fix or next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to Hot Standby)

Page 6 of 10 NUREG-I 021, Draft Revision 9

Op-Test No.:

1 Scenario No.:

3 Event No.:

4 Event

Description:

21 Main Feed Pump Trip Time I

Position Applicant's Actions or Behavior CRS ll Recognizes trip of the operating main feedwater pump. Enters S2.0P-AB.CN-0001 (a), Main Feedwater / Condensate System Abnormality..

I CRS CRS PO Verifies reactor power c P-10 setpoint. Proceeds to Step 3.14.

I Directs RO to reduce power to 4%.

4.

Sets SG Inlet Vlv demand to 0% (Vlvs 21 through 24AF21)

5.

Starts 21 and 22 AFW pumps

6.

Controls 21 through 24AF21 to maintain SG levels within 55% of program level (-35% NR level)

SIMULATOR OPERATOR:

7.

Use RT-4 to trigger next event RCP High Vibration) on after SG level control established or following plant stabilization post-trip on cue from lead examiner.

Page 7 of 10 NUREG-1021, Draft Revision 9

~~

Op-Test No.: 1 Scenario No.:

3 Event No.: 5 Event

Description:

23 RCP High Vibration Time I Position Applicant's Actions or Behavior RO PO Observes OHA D-36 RCP VIB HI alarm. Refers to S2.OP-AR.ZZ-O004(Q),

Overhead Annunciators Window D.

Checks vibration levels behind Panel 2RP4. Determines vibration level on 23 RCP motor flanae > 5 mils.

SIMULATOR OPERATOR:

1.

2.

Increase SG tube leak from 5 gpm to 650 gpm over 1 minute after 23 RCP stopped.

Use RT-5 to trigger next event (Loss of Offsite Power) when SI manually initiated or at discretion of lead examiner.

CRS CRS Page 8 of 10 Implements S2.OP-AB.RCP-0001 (a), Reactor Coolant Pump Abnormality.

Initiates Attachment 1, Continuous Action Summary.

Directs manual reactor trip and stop of 23 RCP after reactor trip confirmed.

NOTE If reactor already tripped, then CRS will direct stopping #23 RCP.

NUREG-I 021, Draft Revision 9

Position RO/PO CRS CRS/RO/PO CRS CRS PO RO PO PO PO CRS PO PO CRS PO Applicant's Actions or Behavior Observe indications of increased rate of 21 SG tube leakage. Informs CRS.

Directs manual SI actuation. Makes page announcement. Transitions to EOP-TRIP-I.

Perform immediate actions of EOP-TRIP-1.

Directs PO to perform APPX-1 to restart CCW pump.

Confirms operability of 4Kv vital buses following loss of offsite power, remains in EOP-TRIP-1.

Op-Test No.:

1 Scenario No.:

3 Event No.:

6 Event

Description:

SGTR with Loss of Offsite Power PO

~~

Blocks and resets SECs Verifies no RCPs running and Tavg 647. (Step 21)

Throttles AFW to maintain SG NR levels 9-35% (Step 21)

Initiates MSL Isolation on loops 21 through 24 (Step 21)

CRITICAL TASK # I Isolate AFW to the ruptured SG within' 10 minutes of initiation of Safety Injection signal.

Isolates AFW to 21 SG Determines 21 SG level increasing in an uncontrolled manner. Transitions to EOP-SGTR-1 (From Step 27 of EOP-TRIP-1)

Verify valves closed on ruptured SG (Step 4)

MS167 MS Stop MS18 MS Bypass MS7 MS Drain GB4 SG Outlet Stops feeding 21 SG (Step 6).

NOTE CRS may direct tripping 23 AFW Pump until stm isolated from 21 SG Resets SI, Phase A, Phase B, SECs, and opens cntmt control air isolation valves 121 CA330 and 22CS330). Resets 230V Control Centers (Stet) 10).

Determines taraet cooldown CET temDerature from Table D.

Cooldowns at max rate using intact SG MSIO valves. Stops cooldown at target temperature.

Depressurizes RCS using PORV NOTE Terminate scenario when depress criteria met (SGTR-1Table F) or at discretion of lead examiner.

Page 9 of 10 NUREG-1021, Draft Revision 9

Time

~

PO Resets A SEC Position Applicants Actions or Behavior PO CRS Determines 21 SI Pump failed to start.

Directs PO to reset SEC and start 21 SI Pumo 1

PO Manually starts 21 SI Pump.

PO Informs CRS.

NOTE Terminate scenario when depress criteria met (SGTR-1Table F) or at discretion of lead examiner.

Page 10 of 10 NUREG-1021, Draft Revision 9

NRC #3 MODE:

2 POWER 3%

RCS BORON:

Mwe:

0 SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS 4000 MWDMTU Reactivity plan for power increase recommends using rod withdrawal to control Tavg during power increase to 18%. Detailed reactivity plan for power increase after turbine sync being developed by Rx engineering MOST LIMITING LCO AND DATE/TIME OF EXPIRATION:

None EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

Plant is recovering fiom a 7 day forced outage to repair a body to bonnet leak on2Ps4. Currently at step 5.4.14 in IOP-3 awaiting Chemistry Department samples. All mode change signoffs are completed.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

PRIMARY:

SECONDARY:

RADWASTE:

Heating steam is aligned to unit 1.

No discharges in progress CIRCULATING WATEWSERVICE WATER: